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Forwards Summary of First 10-yr Inservice Insp Program, Addressing Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1983 Edition Through Summer 1983 Addenda.Fee Paid
	ML20195D687
Person / Time
Site:	Millstone
Issue date:	05/22/1986
From:	Opeka J, Sears C; NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	Noonan V; Office of Nuclear Reactor Regulation
References
	F1000F, NUDOCS 8606050017
	Download: ML20195D687 (107)
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(203) 685-5000 May 22,1986 Docket No. 50-423 F1000F Office of Nuclear Reactor Regulation Attn:

Mr. Vincent S. Noonan, Director PWR Project Directorate #5 Division of PWR Licensing - A U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Reference:

T. M. Novak letter to 3. F. Opeka, Issuance of Facility Operating License NPF-49, dated January 31,1986.

Dear Mr. Noonan:

Millstone Nuclear Power Station, Unit No. 3 License Condition 2.C.5. - ISI Program l

In accordance with Reference 1, Northeast Nuclear Energy Company hereby submits a summary for the first Ten-Year In-Service Inspection Program. The summary addresses the requirements of the ASME Boiler and Pressure Vessel Code,Section XI,1983 Edition, through Summer 1983 Addenda, as amended by 10CFR50.55a(b)(2)(IV)(A).

If there are any questions, please contact our licensing representative directly.

Very truly yours,

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NORTHEAST NUCLEAR ENERGY COMPANY S.3.O J. F. Opeka Senior Vice President By: C. F. Sears i

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that he is Vice President of Northeast Nuclear Energy Company, an Licensee herein, that he is authorized to execute and file the foregoing information in the name and on behalf of th t Licensees herein and that the statements contained in said information are tre; and correct to the best of his knowledge and belief, s

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MILLSTONE UNIT 3 IN-SERVICE INSPECTION PROGRAM SUBMITTAL APPLICATION ABSTRACT This document describes the basis for the rirst Ten-Year in-service Inspection Program for Millstone Unit 3.

This summary addresses the requirements of the ASME Boiler and Pressure Vessel (B&PV) Code, Section-XI, 1983 Edition, through Summer 1983 Addenda, as amended by 10CFR50.55a (b)(2)(iv)(A). Additional requirements for Augmented Inspections are also addressed.

Included are Relief Requests and tables identifying all items subject to

examination by Code Category and Code Item Number.

By law, Millstone Unit 3 is committed, as a minimum, to develop this ISI Program to the 1980 Edition through the Winter 1981 Addenda of Section XI, but has opted to upgrade this program to the 1983 Edition through the Summer 1983 Addenda, per the revision of 10CFR50.55(a) published in the Federal Register Notice Vol. 50, No. 187, dated September 26, 1985.

LIST OF TABLES

- Table 1:

In-service Inspection Program Summary Sheets A.

Class 1 Components Inspection Summary B.

Class 2 Components Inspection Summary C.

Class 3 Components Inspection Summary D.

Class 1, 2, and 3 Component Support Inspection Summary 1

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TABLE OF CONTENTS

--- Cover Sheet / Approvals

--- Abstract

--- Table of Contents

--- List of Tables

1.0 INTRODUCTION

1.1 General 1.2 Applicable Editions and Addenda to Section XI 1.3 System Classification 1.4 Inspection Program

2.0 DESCRIPTION

OF INSPECTION PROGRAM 2.1 Class 1 2.1.1 ASME Code Exemptions Employed 2.1.2 Component / Piping Examination Development 2.1.3 Steam Generator ECT Exams 2.1.4 System Pressure Tests 2.2 Class 2 2.2.1 ASME Code Exemptions Employed 2.2.2 Component / Piping Examination Development 2.2.3 Augmented Inspection Requirements 2.2.4 System Pressure Tests 2.3 Class 3 2.3.1 ASME Code Exemptions Employed 2.3.2 System Pressure Tests 2.4 ASME Class 1, 2, and 3 Component Supports 2.4.1 ASME Code Exemptions Employed 2.4.2 Class 1 Supports 2.4.3 Class 2 Supports 2.4.4 Class 3 Supports 3.0 RELIEF REQUESTS 3.1 General 3.2 Listing of Applicable Relief Requests 3.3 Complete Relief Requests, IR-1 through IR-11

4.0 EVALUATION CRITERIA 4.1 Class 1 Acceptance Standards 4.2 Class 2 Acceptance Standards 4.3 Class 3 Acceptance Standards 4.4 Acceptance Standards for Supports (Classes 1, 2, and 3) 5.0 SUBMITTAL

SUMMARY

5.1 Description of ISI Plan Format 5.2. Description of Summary Submittal Tables 6.0 RECORDS AND DATA MANAGEMENT 7.0 FIGURES AND ATTACHMENTS 7.1 Figures 7.2 Attachments

1.0 INTRODUCTION

1.1 General 1.1.1 This Summary Submittal describes the Millstone Unit 3 first Ten-Year In-service Inspection Plan.

The Inspection Plan, which consists of ASME Class 1, 2, and 3 systems and components (and their supports) has been developed by giving due consideration to the following documents:

o 10CRF50.55(a) o Section XI of the ASME Code, 1983 Ed., through 1983 Summer Addenda o

Section III of the ASME Code o

Section V of the ASME Code o

USNRC Standard Review Plan (SRP 6.6, Section II-7) o USNRC Regulatory Guides:

Regulatory Guide 1.14, Rev. 1, August 1975 Regulatory Guide 1.26, Rev. 3, February 1976 Regulatory Guide 1.65, Rev. O, October 1973 Regulatory Guide 1.83, Rev. 1, July 1975 Regulatory Guide 1.147, Rev. 4, September 1985 Regulatory Guide 1.150, Rev.

1, February 1983 o

ASME Code Case N-408 o

Millstone Unit 3-FSAR Millstone Unit 3-PSI Inspection Plan (PSI-2.01) o 1.1.2 The program for in-service testing of Class 1, 2, and 3 pumps and valves and pressure testing of Class 1, 2, and 3 systems was addressed separately and submitted for NRC review and comment in October 1985.

1.1.3 The preservice inspection was conducted in accordance with the 1980 Edition through Winter 1980 Addenda of Section XI of the ASME-B&PV Code.

1.2 Applicable Editions and Addenda to Section XI Pursuant to Title 10 of the Code of Federal Regulations, Part 50, Paragraph 50.55(a), and the Federal Register Notice, Vol. 50, No. 187, dated September 26, 1985, the in-service inspection requirements applicable to nondestructive examina-tion and system pressure testing at Millstone Unit 3 are based on the rules set forth in the 1983 Edition of ASME Section XI through Summer 1983 Addenda, hereinafter referred to as ASME Section XI. - - - -

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As permitted by Paragraph 50.55a(g)(4), NNECO may elect, for l

certain components, to meet supplemental requirements as set forth in the Editions and Addenda of the Code which became effective subsequent to the 1983 Edition through the Summer 1983 l

Addenda of ASME Section XI.

Other editions and addenda of ASME Section XI or ASME Code cases that are adopted will be identified l

in the appropriate sections of this inspection program.

It is the intent of NNECO to continually apply appropriate changes of the Code, with NRC approval, which improve the overall quality of Millstone Unit 3's Inspection Programs.

j 1.3 System Classification 1

1.3.1 The Construction Permit for Millstone Unit 3 was issued in August 1974. The Operating License was issued in January 1986. Northeast Nuclear Energy Company is the owner of record, Stone & Webster was the A/E and installer of record.

1.3.2 Vessels, piping, pumps, and valves were built and installed according to the rules of ASME Section III for those systems classified as Class 1, 2, and. 3.

t 1.3.3 The system classifications used as a basis for the

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In-service Inspection Plan are based on the require-ments of 10CFR50 and Regulatory Guide 1.26.

1.3.4 Class 1 System Boundaries were developed based on 10CFR50.2(v).

1.3.5 Class 2 and 3 System Boundaries were developed based on Regulatory Guide 1.26.

i 1.3.6 System Boundary diagrams are provided to show the specific boundaries for the Class 1, 2, and 3 systems.

From these drawings, the In-service Inspection Plan has been developed.

1.4 Inspection Program Examinations for the Ten-Year Interval will be scheduled in accordance with Inspection Program B, as described in IWA-2400 of ASME Section XI, for all Class 1, 2, and 3 systems, components, and supports. _ _ _ _ _ _ _

2.0 DESCRIPTION

OF THE INSPECTION PROGRAM The following is a detailed description of the Inspection Plan Basis for each component and/or system to be examined.

2.1 Class 1 Systems The Class 1 System Boundaries are developed based upon the sequirementa ut 10CRF50.2(v) anid Llie flillaluite Untit 3 F3Ali.

The components / systems to be examined in the Class 1 Systems are described in detail belov:

2.1.1 ASME Code Exemptions Employed 2.1.1.1 IWB-1220 The following components (or parts of components) are exempted from the volumetric and surface examination requirements of IWB-2500:

a)

Component connections, piping, and associated valves of one inch nominal pipe size and smaller, except for steam generator tubing.

b)

Reactor vessel head connections and associated piping, two inch nps and smaller, made inaccessible by control rod drive penetrations.

2.1.2 Component / Piping Examination Development 2.1.2.1 Reactor Pressure Vessel (RPV) and RPV Closure Head Inspections of the Millstone Unit 3 Reactor Pressure Vessel will be conducted, in accordance with Table IWB-2500-1 of ASME Section XI.

Refer to Section 7.2, Table A, of this submittal for Inspection Summary of Class I components.

Refer to Relief Request IR-1 and IR-2 for areas not examinable.

The RPV examinations will be performed to meet the intent of the requirements of Regulatory Guide 1.150 and ASME Section XI.

2.1.2.2 Steam Generators (Primary Side)

All examinations are performed, in accordance with Table IWB-2500-1. Refer to Section 7.2, Table A, of this submittal for Inspection Summary of Class I components.

Nozzle inner radius exams are the subject of Relief Request IR-5.

Also, see Relief Request IR-2 for areas not examinable.

2.1.2.3 Pressurizer All examinations are performed in accordance with Table IWB-2500-1. Refer to Section 7.2, Table A, of this submittal for Inspection Summary of Class I components.

Refer to Relief Requests IR-2 and 3 for areas not examined. Relief Request IR-5 covers nozzle inner radius exams.

2.1.2.4 Reactor Coolant Pressure Boundary Piping Welds on piping greater than one inch nominal pipe size are selected for examina-tion in accordance with Table IWB-2500-1, categories B-F and B-J.

Refer to Section 7.2, Table A, of this submittal for inspection summary of Class I components.

Refer to Relief Request, IR-11 for areas of welds not examinable.

2.1.2.5 Reactor Coolant Pumps As required by Regulatory Guide 1.14, the bore and keyway areas of each RCP flywheel are examined ultrasonically once each period. Additionally, the flywheels receive a 100 percent volumetric examination (UT) and a surface examination near the end of each Inspection Interval.

Visual exams of the pump casing internal pressure boundary surfaces will be performed only if a pump is disassembled for maintenance (see Relici Request IR-4). --

l 2.1.3 Steam Generator ECT Examinations The steam generator tubing surveillance requirements are contained in the Unit 3 Plant Technical Specifica-tions. The exam requirements are based on Regulatory Guide 1.83, Revision 01, and ASME Section XI, which contains the requirements for sampling, acceptance, plugging, and reporting.

l 2.1.4 System Pressure Tests - Class 1 2.1.4.1 System pressure tests are conducted on l

Class 1 systems and components as required by Table IWB-2500-1, Examination Cate gory B-P.

A system leakage test and a system hydrostatic test is performed in accordance with IWB-5221 and IWB-5222, respectively.

2.1.4.2 The system boundaries subject to system leakage and system hydrostatic tests, as well as the test program, are included in the In-service Test Program which has been l

submitted separately.

2.2 Class 11 Systems The Class 2 System Boundaries are developed based upon the requirements of Regulatory Guide 1.26 and Millstone Unit 3-FSAR.

Specific examination requirements for specific components and systems are based upon the requirements of ASME Section XI and as modified by 10CFR50.55a, Paragraph (b)(2)(IV)A, and ASME Code Case N-408.

Supplemental examinations required by Standard Review Plan SRP 6.6, Section II-7, are also incorporated where applicable.

Details of how all requirements are factored into the Class 2 Program are delineated in Paragraph 2.2.2 below:

2.2.1 ASME Code Exemptions Employed Code Case N-408, Alternative Rules for Examination of Class 2 Piping,Section XI, Division 1.

2.2.1.1 For welds in austenitic stainless steel or high alloy piping, the requirements of Table 1, Examination Category C-F-1, Pressure Retaining Welds in Austenitic Stainless Stect or liigh Alloy Piping, shall be used as an alternative to the require-ments of Table IWC-2500-1. - -

2.2.1.2 For welds in carbon or low alloy steel piping, the requirements of Table 2, Examination Category C-F-2, Pressure Retaining Welds in Carbon or Low Alloy Steel Piping, shall be used as an alter-native to the requirements of Table IWC-2500-1.

2.2.2 Component / Piping Examination Development 2.2.2.1 Steam Generators (Secondary Side)

All volumetric examinations are performed in accordance with Table IWC-2500-1 of ASME Section XI.

Refer to Section 7.2 Table B, of this submittal for Inspection Summary of Class 2 components.

See Relief Request IR-5 for nozzle inner radii.

2.2.2.2 Residual Heat Removal Heat Exchangers All examinations will be performed in accordance with Table IWC-2500-1 of ASME Section XI.

The inlet and outlet nozzles (Class 2 side) of both heat exchangers are obstructed from NDE examination and will be examined in accordance with the examination requirements of Code Cater / C-B, Item C2.30.

Refer to Section 7.2, Table B, of this submittal for Inspection Summary of Class 2 components.

2.2.2.3 Main Steam and Feedsater Piping Piping welds are selected for examination based upon the requirements of Code Case N-408, Table 2, Code Category C-F-2.

In addition, high stress welds that exceed the criteria of Note la in the 1983 Edition of Section XI, Category C-F, shall be examined.

Augmented examination requirements of SRP 6.6 shall also be included.

Refer to Section 7.2, Table B, of this submittal for Inspection Summary of Class 2 components, i,

l

r 2.2.2.4 Austenitic Piping Systems Examination requirements for the austenitic Class 2 piping systems, both volumetric and surface examinations, including weld selection, are developed based upon the requirements of ASHE Section XI, Code Case N-408, Table C-F-1.

Refer to Section 7.2, Table B, of this submittal for Inspection Summary of Class 2 components.

2.2.3 Augmented Inspection Requirements Augmented examinations are incorporated into the In-service Inspection Program per the following criteria:

2.2.3.1 Augmented ISI to Protect Against Postulated Piping Failures (SRP 6.6)

Class 2 high energy systems piping greater than four inches NPS between containment isolation valves shall be volumetrically examined (100 percent of circumferential and longitudinal welds). The areas subject to examination are defined in accordance with Examination Category C-F for Class 2 piping welds and are specifically denoted in the Inspection Plan as requiring aug-mented inspection.

The systems which are affected are:

a)

Main Steam System (HSS) b)

Main Feedwater System (FWS) c)

Low Pressure Safety Injection System (SIL) d)

Turbine Plant Drains (DTM) 2.2.3.2 Augmented examination in the break exclusion areas specified in the HP-3 FSAR, Section 3.6, will be conducted as follows on lines equal to or less than four inches NPS.

Lines greater than four inches are examined to meet the requirements of Paragraph 2.2.3.1 above. All welds in the following systems, defined as B.E.A. welds, will receive surface examinations only for ISI, as authorized by the NRC for preservice considerations in January I'385..

The systems which are effected are:

a)

Steam Generator Blowdown (BDG) b)

Main Steam Piping (MSS) c)

Chemical and Volume Control (CHS) d)

Feedwater System (FWS) e)

Auxiliary Feedwater (FWA) f)

liigh Pressure Safety Injection (SIH) g)

Turbine Plant Drains (DTM)

Refers to Section 7.2, Table B, of this submittal, for inspection summary of Class 2 components.

2.2.4 System Pressure Tests - Class 2 2.2.4.1 The pressure retaining components within the Class 2 system boundaries are subjected to System Pressure Tests as required by Table IWC-2500-1, Examination Category C-l!.

System Functional Tests, IWA-5211(b) and System liydrostatic Tests, IWA-5211(d) will be performed in accordance with IWC-5210.

2.2.4.2 The boundaries subject to system pressure tests (functional and hydrostatic), as well as the test program, are included in the In-service Test Program which has been submitted separately.

2.3 Class 3 The Class 3 System Boundaries examinations are developed based upon the requirements of Regulatory Guide 1.26 and Millstone Unit 3-FSAR.

2.3.1 ASME Code Exemptions Employed 2.3.1.1 IWD-1220.1 - Integral attachments of supports and restraints, to components that are 4 inches nominal pipe size and smaller, within the system boundaries of Examination i

Categories D-A, D-B, and D-C of Table IWD-2500-1, shall be exempt from the visual examination VT-3, except for the Auxiliary l

Feedwater Systems.

2.3.1.2 IWD-1220.2 - Integral attachments of supports and restraints, to components exceeding 4 inches nominal pipe size, may be exempted provided:,

(a) The components are located in systems (or portions of systems) whose function is not required in support of reactor residual heat removal, containment heat removal, and emergency core cooling.

(b) The components operate at a pressure of 275 psig or less and at a tempera-ture of 200 degrees Fahrenheit or less.

2.3.3 System Pressure Tests - Class 3 2.3.3.1 The pressure retaining components within tie boundary of each system specified for E.camination Categories D-A, D-B, and D-C are pressure tested and visually examined as specified in Table IWD-2500-1. A System a

In-service Test, IWA-5211(c), System Functional Test, IWA-5211(b), and System llycrostatic Test, IWA-5211(d) will be performed in accordance with IWD-5221, IWD-5222, and IWD-5223, respectively.

Refer to Section 7.2, Table C, of this submittal for Inspection Summary for Class 3 components.

2.3.3.2 Th.! boundaries subject to system pressure te sts (Functional, In-service, and liydrostatic),

as well as the test programs are included ir the In-service Test Program which has been submitted separately.

2.4 ASME Class 1, 2, and,3 Component Supports ASME Code Class 1, 2, and 3 component supports are examined in accordance with the requirements of IWF-2500. The detailed selection criteria is as follows:

Component supports select?d for examination shall be supports of those components that 4.re required to be examined under IWB, IWC, and IWD.

2.4.1 ASME Code Exemptions Employced 2.4.1.1 Component supports of those components that are req,. ired to be examined under IWE. The requireu nts of subsection IVE are not imposed on the licensee by 10CFR50.55a.

9

2.4.2 class 1 Component Supports Class 1 piping and component supports are visually examined (VT-3) to determine their general mechanical and structural integrity and, where appropriate, to determine conditions relating to their operability (VT-4). Class I supports subject to examination are selected, in accordance with subarticle IWF-2510 of ASME Section XI.

Refer to Section 7.2, Table D, of this submittal for Inspection Summary of Class 1, 2, and 3 component supports.

2.4.3 Class 2 Component Supports Piping and component supports are visually examined (VT-3) to determine their general mechanical and structural integrity and, where appropriate, to determine conditions relating to their operability (VT-4). The Class 2 supports subject to examination have been selected, in accordance with subarticle IWF-2510 of ASME Section XI.

Refer to Section 7.2, Table D, of this submittal for Inspection Summary of Class 1, 2, and 3 component supports.

2.4.4 Class 3 Component Supports Class 3 piping and component support integral attach-ment welds, except those exemj.ted by IWD-1220.1 and IWD-1220.2, are visually examined (VT-3). Other Class 3 piping and component supports are visually examined (VT-3) to determine their general mechanical and structural integrity and, where appropriate, to determine conditions relating to their operability (VT-4). The Class 3 supports subject to examination have been selected, in accordance with subarticle IWF-2510 of the ASME Section XI.

Refer to Section 7.2, Table D, of this submittal for Inspection Summary of Class 1, 2, and 3 component supports..

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3.0 RELIEF REQUESTS 3.1 General 3.1.1 During Preservice Inspection, there were cases where component configuration and/or interferences prohibited 100 percent coverage of the Code required volume or surfaces.

In each case, where such limitations were encountered, the details are documented in a Relief Request. Since those same conditions will prevail during this In-service Inspection Interval, those Relief Requests are included that will be utilized in the First ISI Interval.

3.1.2 In cases where parts of the required examination areas cannot be effectively examined, because of a combination of component design or current inspection technique limitations, NUSCO will continue to evaluate the development of new or improved examination techniques, with the intent ot' applying these techni-ques where a practical improvement in the examination can be achieved.

t 3.1.3 Format - Relief Requests are arranged in order by Code Category. They are numbered sequentially. Each Relief Request contains the following information:

a.

Component Identification - describes the Code Class, Code Examination Category (if applicable), and a brief description.

b.

Examination Requirement - describes the Code Item Number (s) and the examination requirement.

c.

Code Relief Requested - self explanatory.

d.

Reason for Relief - describes examination (s) conducted and/tr evaluated to support the basis for relief, c.

Proposed Alternative Examination - self-explanatory.

3.2 Relief Request and Tables l

3.2.1 The format described above is designed to be brief, clear, and concise.

Where applicable, supportive documentation in the form of Tables l

and Figures (referenced by the Tables), specif-l ically identify each item affected by the Relief Request and describe the limitations encountered and the extent of examination achieved during Preservice Examination and which is expected to remain unchanged for the First Ten-Year ISI Interval. I l

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3.2.2 Relief Requests known to be applicable to ISI examinations are listed below. Additional Relief Requests, as deemed necessary, will be

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submitted pursuant to the requitements of 10CFR50.55a(g)(5).

3.3 Complete Relief Request 3.3.1 IR-1 IR-4 IR-8 IR-2 IR-5 IR-11 IR-3

Complete relief requests referenced above (Attached)*

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P.111 stone Nuclear Power Station Unit No. 3 Relief From In-Service Inspection Requirements Relief Request:

IR-1 Pressure retaining welds in reactor vessel.

Component Identification:

Code Class:

1 Examination Category:

B-A and B-D Code Requirement:

For Millstone Unit No. 3 a volumetric (ultrasonic) examination of essen-tially 100 percent of the weld length shall be conducted for the following items in accordance with ASME B & PV Code, 1983 through the Summer 1983 Addenda, Article IWB-2500:

Ites Description e

B.1.12 Longitudinal shell welds B.1.21 Head circumferential welds B.1.22 Lower head meridional welds 3.1.30 Shell-to-Flange weld

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B.3.90 Nozzle to shell welds B.3.100 Nozzle inner radius areas Code Relief Request:

Pursuant to 10CFR50-50(a)(3)5(iii), relief is requested from performing the in-service volumetric examination of the inaccessible portion of the subject vessel welds.

Basis for Relief:

Geometric configuration and permanent obstructions affected the attached matrix of welds f rom performing a 100 percent volumetric examination.

The ISI limitations and the specific relief as they apply to each weld, are noted in the attached.

The subject welds received both volumetric examination by radiography and surface examinations during fabrication, in accordance with ASME Section 111 requirements which provide adequate assurance of the structural integrity of the welds.

Support for_ Relief / Alternate Examinations:

A.

The subject welds will receive a volumetric examination on the accessible portions in accordance with Section XI (IWB-2500-1).

B.

An in-service hydrostatic test will be conducted on the Class 1 pressure boundary of which these welds are a part thereof (IWB-2500-1).

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In-service system leakage tests will be performed per Category B-P, IWB-2500-1.

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e WELD NO./ DESCRIPTION MANUAL REMOTE C0ffENTS 9

1 Seal Surface Portion None N/A Normal component geometry. Responses noted from flange taper and stud holes.

No inservice limitations anticipated.

1 Vessel I.D. Portion N/A None Normal flange geometry noted. No inservice limitations anticipated.

2 Upper to Interm. Cire.

N/A None Transition weld. No significant limitations anticipated providing future exams.

Include a program to examine through the taper section. For full Sec. XI coverage.

3 Interim. to Lower Ci re.

N/A None None

4 Lower Shell to Lower Head N/A Core Lugs A.

100 percent accessible from the lower head side.

(Examined with 45* and 60*

axially [one direction] and circum-ferentially [both directions].)

R.

70 percent accessible from the lower shell side.

(Examined axially and circum-ferentially.) Six core lugs occupying a total of about 17* each, preclude four directional examination of about 153" of weld 4 as examined from the lower shell side.

NOTE: Core lug obstructions are considered normal in the in-service examination of lower shell to lower head welds from the shell side. No special considerations are necessary for future examinations other than an estimate of the examination not practical from both directions due to restrictions, a

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WEI.D NO./ DESCRIPTION MANUAL REMOTE COMMENTS

5 Torus to Dollar Plate Instrument Tubes Instrument Tubes A.

Remote Examination - Not performed PSI. Should not be attempt'ed in-service -

reason - density of instrument tubes precludes the taking of meaningful data by remote means from the vessel interior.

B.

Manual Examination - (O.D.) 5 percent limitation noted, 95 percent coverage four directional with manual technique.

(Reference Figure 1A and IB weld 5 limitations.)

NOTE:

In-service examination requirements for weld 5 can be satisfied with the manual O.D. inspection only.

Weld 15, 16, 17, 18 Bottom Meridional to Instrument Tubes A.

Remote Examination - Performed four Bottom Head Meridional weld 4 junction (Major limitation) directional with 0, 45* and 60* across Welds (Minor limitation) 45 percent of each meridional weld length. Extent of remote examination noted in Figure 2.

B.

Manual Examination - (O.D.) - Performed four directional with 0*, 45* and 60*

across 100 percent of the length of each meridional weld. Welds 15, 17, and 18 were examined to 98 percent of the required volume with a limitation at the taper junction of weld 4 and a taper and weld configuration limitation which resulted in 93 percent of weld 16 being examined.

NOTE:

In-service examination requirements of the meridional welds can be satisfied with O.D. examinations of the length estimated to be not available for remote I.D. examination (with overlap for conservatism).

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1 Pag 2 3 ef g

s PSI /ISI LIMITATI6.

s.

WELD NO./ DESCRIPTION MANUAL REMOTE COMMENTS T

Welds 6, 7, 8 N/A Normal nozzle PSI AND ISI will be conducted to j

Upper shell long.

geometry maximum extent practical. Reference (Major limitation)

Figure 3 will be examined similarily at the end of the first interval.

Weld 9, 10, 11 N/A None Weld + 1/2T requirement for veld 9, 10, Interm. shell long.

and 11 at the 127" level is satisfied to the maximum extent practical by the weld 2 taper routine.

Weld 12, 13, 14 N/A None None j

Lower shell long.

Outlet nozzle to shell Normal nozzle None Nozzle to Shell:

i Welds 19, 22, 23, 26 radius configur-A.

Remote: - From nozzle bore only with NEU-1-Il00A sketch ation angles essentially perpendicular to the weld.

B.

Manual: - Examined tangentially from l

vessel interior (30 percent volume not examinable - nozzle radius configuration).

l l

Nozzle inside Radius: Volume MNOP f

i Figure IWB 2500 - 7(a) W80

)

Outlet nozzle protrusion None N/A A.

Remote: - From nozzle bore TR 7 & 8 (60 ).

i radius B.

Manual: - To examine edge for corner flaw.

t j

NOTE:

(Inside Radius) The Utility may elect to:

j 1.

Apply contact examination methodology in-service if a high degree of assurance exists that such methods will provide meaningful results.

2.

Seek relief from volumetric examination and perform visual examination instead.

(End of L

j interval exam.)

i 1

Inlet nozzle to shell Normal nozzle None A.

Remote - From nozzle bore only with test i

Welds 20, 21, 24, 25 radius configur-angles essentially perpendicular to the weld.

I ation B.

Manual - Examined tangentially from vessel interior 15 percent of required volume detepnined i

{

notexaminable(nozzlppadiuscon{igurapion).

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WELD NO./ DESCRIPTION MANUAL REMOTE COMMENTS Inlet nozzel inside radius None N/A Nozzle Inside Radius:

section A.

Remote - From nozzle bore TR 7 & 8 (60*).

B.

Manual - To examine edge for corner flaw.

NOTE:

(Inside Radius) The Utility may elect to:

1.

Apply contact examination methodology in-service if a high degree of confidence exist that meaningful results can be obtained.

2.

Seek relief from volumetric examination and perform visual examination instead.

(End of interval.)

1-54 None N/A None Threads in flange (Ligaments)

Inlet and outlet nozzle N/A None NOTE: CODE REQUIRED INNER 1/3 is best examined from the 0.D. where practical. Complimenta ry remote / manual exams are optimum for ISI.

Inlet and outlet spool to N/A None Same note as above.

R.C. pipe welds h

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Millstone Nuclear Power Station Unit No. 3 k_/

Relief From In-Service Inspection Requirements Relief Request:

IR-2 Component Identification:

Pressure retaining welds in reactor vessel closure head.

Code Class:

1 Examination Category:

B-A Code Requirement:

For Millstone Unit 3, a volumetric examination of essentially 100 percent of the weld length shall be conducted for the following items in accordance with ASME B&PV Code, 1983 Edition through the Summer 1983 Addenda, Article IWB-2500:

Item Description 4

Bl.21 Circumferential head weld Bl.22 Meridional head weld Bl.40 Head to flange weld.

g Code Relief Request:

( /

Pursuant to 10CFR50.55(a)(g)S(iii), relief is requested from performing the in-service volumetric examination of the inaccessible portions of the subject vessel welds.

Basis for Relief:

Geometric configuration and permanent obstructions limited the volumetric examination of the following listed welds. Examination data sheets and limitation sketches (attached) depict the affected areas. Relief is therefore requested on complying with the 100 percent weld required volume (WRV) coverage of these welds.

1.

Weld No. 101-101 Head to Flange Weld.

Access to this weld is limited to essentially one side only due to the forged flange configuration. Additional limitation from the top side of the weld are due to permanently attached head lif ting lugs.

Required volume not examinable ~ 33 percent.

2.

Weld No. 103-101 Circumferential Head Weld.

Permanently attached head lif ting lugs prevent volumetric examina-tion of ~ 7 perent of the WRV.

3.

Weld No. 101-104D Meridional Head Weld.

LMW51171

I A 2.7" diameter repair area (surface concavity) on the weld center-line prohibited sufficient coverage of the WRV in that area.

s Required volume not examinable ~ 2 percent.

The subject welds received both volumetric examination by radiography and surface examinations during fabrication in accordance with ASME Section III requirements which provide adequate assurance of the structural integrity of the welds.

Support for Relief / Alternate Examinations:

1.

The subject welds will receive a volumetric or volumetric and surface

~~;

I examination on the accessible portions as required by Section XI l

(IWB-2500-1).

2.

An in-service hydrostatic test will be conducted on the Class 1 Pressure Boundary of which these welds are a part thereof (IWB-2500-1).

3.

In-service system leakage tests will be performed per Category B-P, IWB-2500-1.

4 1

0 DfW51171

WESTINGHOUSE ELECTRIC CORPORATION

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PROVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE. LOCATION AND TYPE OF INDIC ATICN CESCRIBE E FTa A OR SPECI AL EOUlPVENT IF USED FOR SIZING OR REPCRTI'dG. f r NECESS AR Y INCLUCE SKETCH SHOWING GENER AL CONFIGUR ATION OF ITEM OR ARE A.

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Millstone Nuclear Power Station Unit No. 3 Relief From In-Service Inspection Requirements Relief Request:

IR-3 Component Identification:

Pressure retaining welds in vessels other than reactor vessels.

Code Class:

1 Examination Category:

B-B Code Requirement:

For Millstone Unit 3, a volumetric examination of essentially 100 percent of the weld length shall be conducted for the following items in accordance with ASME B&PV Code, 1983 Edition through the Summer 1983 Addenda, Article IWB-2500:

Item Description B2.11 Circumferential Shell-to-Head Welds (Pressurizer)

B2.12 Longitudinal Shell Welds (Pressurizer)

B2.40 Tube Sheet-to-Head Welds (Steam Generators)

-s Code Relief Request:

\\s_

Pursuant to 10CFR50.55(a)(g)5(iii), relief is requested from performing the in-service volumetric examination of the inaccessible portions of the subject vessel welds.

Basis for Relief:

Geometric configuration and permanent obstructions limited the volumetric examination of the following listed welds. Examination data sheets and limitation sketches depict the affected areas. Relief is therefore requested on complying with the 100 percent WRV coverage of the welds.

Pressurizer 1.

03-007-SW-J - Shell-to-Upper-Head Weld Permanently installed insulation support ring obstructed part of the required scanning area.

Required volume not examinable ~ 9 percent.

2.

03-007-SW-F - Shell-to-Lower-Head Weld Permanent obstructions (alignment target pads and instrumentation lines) and the geometric configuration--weld transition between plate thickness variations prohibited complete coverage.

s

\\s_,/

Required volume not examinable ~ 30 percent.

JAG 510291

3.

03-007-SW-A - Longitudinal Seam Weld Permanently installed insulation support ring obstructed part of the required scanning area.

Required volume not examinable ~ 5 percent.

Steam Generators 4

1.

03-003-SW-Z S/G A 03-004-SW-Z S/G B 03-005-SW-Z S/G C 03-006-SW-Z S/G D Permanent obstructions--permanent I beam support columns for each generator restricted scans as shown on the attached sketch.

Required volume not examinable ~ 30 percent.

Support For Relief (Alternate Examinations):

A.

The subject welds will receive a volumetric examination on the accessible areas in accordance with Section XI (IWB-2500-1).

B.

A Section III hydrostatic test will be conducted on the Class I pressure boundary of which these welds are part thereof (IWB-2500-1).

C.

In-service system leakage tests will be performed per Category B-P, IWB-2500-1.

O JAG 510291 n

n f

Millstone Nuclear Power Station Unit No. 3

v Relief From In-service Inspection Requirements Relief Request:

IR-4 Component Identification:

Code Class:

1 Examination Category:

B-L-2 and B-M-2 Code Requirement:

For Millstone Unit No. 3, a visual examination (VT-3) of the internal surfaces shall be conducted for the following items in accordance with ASME B&PV Code, 1983 Edition through the Summer 1983 Addenda.

Item Description B12.40 Valve bodies exceeding 4" NPS B12.20 Pump casings Note: Examinations are limited to:

(

A.

One valve within each group of valves that are of the same design, manufacturing method, and are performing similar functions in the system.

B.

One pump per group performing similar functions.

Code Relief Request:

Pursuant to 10CFR50-55(a)(g)S(iii), relief is requested from performing an in-service visual examination (VT-3).

Support for Relief / Alternate Examinations For the reactor coolant pump casings and 35 valve bodies (see attached list) in the reactor coolant, pressurizer, safety injection, and residual heat removal systems, relief is requested from disassembly of an operable valve or purp for the performance of an in-service visual examination (VT-3).

The requirement to disassemble an operable valve or pump for the sole purpose of performing a visual examination (VT-3) of the internal pressure retaining boundary is impractical and not commensurate with the increased safety achieved by this inspection. To disassemble these items would provide a very small potential for increasing plant safety margins with a o

disproportiona_te impact on expenditures of plant manpower and resources.

U LMW511263

l Class 1 valves and pu;sps are subjected to numerous types of nondestructive i

testing in accordance with ASME Section III and a rigorous quality assurance program during all stages of fabrication, storage, and instal-lation. These valves and pumps have been found acceptable by the manu-facturer, the ASME Authorized Nuclear Inspector, and Northeast Utilities' i

Quality Assurance. Class 1 pumps and valves will receive visual examination (VT-3) in-service when they are disassembled for maintenance or purposes 4

j other than ISI.

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CLI Page 1 g

Operator Zone Valve / Pump No.

Line No.

Instrument No.

8 RCS-PIA Reactor Coolant Pump 9

RCS-PIB Reactor Coolant Pump 10 RCS-PIC Reactor Coolant Pump 11 RCS-PID Reactor Coolant Pump 12 V2 3-RCS-29-2-1 NV-8001A 12 VIA 3-RCS-275-5-1 MV-8002A 13 V3 3-RCS-275-10-1 MV-8002B 13 V4 3-RCS-029-7-1 MV-8001B 14 V6 3-RCS-029-12-1 MV-8001C 14 V5 3-RCS-275-15-1 MV-8002C 15 V8 3-RCS-029-17-1 MV-8001D 15 V7 3-RCS-275-20-1 MV-8002D 4

20 V173 3-RCS-006-84-01 SV-8010C 20 V172 3-RCS-006-83-01 SV-8010E 4

20 V171 3-RCS-006-82-01 SV-8010A

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22 V987 3-SIL-006-139-01 Check g

22 V15 3-SIL-010-45-01 Check 22 V30 3-RCS-010-122-01 Check 23 V71 3-RCS-010-132-1 Check 23 V986 3-RCS-006-140-1 Check 23 V17 3-SIL-005-5-1-1 Check 24 V26 3-SIL-008-155-1 Check 24 V932 3-SIL-006-161-1 Manual 24 V69 3-SIL-006-21-1 Check 25 V107 3-RCS-010-138-1 Check 25 V985 3-SIL-006-145-1 Check 25 V19 3-SIL-010-49-1 Check 26 V146 3-RCS-010-146-1 Check 26 V21 3-SIL-010-51-1 Check 26 V984 3-SIL-006-146-1 Check 27 V999 3-RCS-012-123-1 MV-8701C 27 V997 3-RHS-012-33-1 MV-8701A t

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CLI Page 2 1,

Operator Zone Valve / Pump No.

Line No.

Instrument No.

i 27 V26 3-SIH-006-59-1 Check 28 V933 3-SIL-006-25-1 Manual i

28 V142 3-SIL-006-25-1 Check

)

28 V996 3-RHS-012-35-1 MV-8702B a'

28 V28 3-SIL-008-156-1 Check 28 -

V998 3-RCS-012-103-1 MV-8702C 29 V9 3-RCS-008-025-1 MV-8003A 30 V53 3-RCS-008-30-1 MV-8003B i

31 V87 3-RCS-008-035-1 MV-8003C f

32 V128 3-RCS-008-40-1 MV-8003D j

39 V102 3-RCS-006-120-01 Check

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_. - _,. _ _ _ _ _. ~ _ _ - _ -. - _

RELIEF FROM IN-SERVICE INSPECTION REQUIREMENTS Relief Request:

IR-5 Component Identification:

Code Class:

1 Examination Category:

B-D Code Class: 2 Examination Category:

C-B Code Requirement:

For Millstone Unit No. 3, a volumetric (ultrasonic) examination of nozzle inner radius sections for the steam generator and pressurizer shall be conducted in accordance with ASME B&PV Code, 1983 Edition through Summer 1983 Addenda, Articles IWB-2500 and IWC-2500, for Code Classes 1 and 2, respectively.

Code Relief Request:

Pursuant to 10CFR50.55(a)(g)5(iii), relief is requested from performing the in-service volumetric examination of the nozzle inner radius sections of the steam generator and pressurizer as listed below:

Component Nozzle (IR)

Class 1 Pressurizer Surge 03-007-SW-S(IR)

Spray 03-007-SW-E(IR)

Class 1 Pressurizer Relief 03-007-SW-D(IR)

Class 1 Pressurizer Safety 03-007-SW-A(IR)

Class 1 Pressurizer Safety 03-007-SW-B,(IR)

Class 1 Pressurizer Safety 03-007-SW-C(IR)

Class 1 Steam Generator Primary Inlet 03-003-IR Primary Inlet 03-004-IR Primary Inlet 03-005-IR Primary Inlet 03-006-IR Class 1 Steam Generator Primary Outlet 03-003-IR Primary Outlet 03-004-IR Primary Outlet 03-005-IR Primary Outlet 03-006-IR Class 2 Steam Generator Feedwater 03-053-SW-R-IR Feedwater 03-054-SW-R-IR Feedwater 03-055-SW-R-IR Feedwater 03-056-SW-R-IR v

G

,_.-.__..__.,,___,,._n g

ps Class 2 Steam Generator Steam Outlet 03-053-SW-T-IR

\\

Steam Outlet 03-054-SW-T-IR Steam Outlet 03-055-SW-T-IR Steam Outlet 03-056-SW-T-IR

Reason for Request

1.

Currently available ultrasonic examination techniques do not provide results which yield a meaningful inspection for comparison with subsequent examinations. This is a result of complex geometrical configuration, long metal paths, limited accessible scan areas, and cladding on some of the nozzles. Refer to the attached drawings of the applicable nozzles depicting the eneplex geometries.

2.

The areas involved have received extensive surface examination during fabrication and reveal no indications of cracking.

In addition, the general area has been examined with ultrasonics during PSI nozzle to vessel weld examinations.

Proposed Alternative Examination 1.

NNECO will assemble a file of as-built information for each of the a

steam generatoi and pressurizer nozzles to support application of new examination techniques during ISI. This information will include factors which could impact a sound beam directed at this area from the OD.

2

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2.

Follow industry progress with technique development and work towards the performance of a meaningful ultrasonic examination during in-service inspection.

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I Millstone Nuclear Power Station Unit No. 3 Relief From In-service Inspection Requirements Relief Request:

IR-8 Component Identification:

Code Class:

1 Examination Category:

B-D Code Ites No(s): B3.110 and B3.130 Code Requirement:

For Millstone Unit No. 3, volumetric (ultrasonic) examination of 100 percent of the full penetration nozzle to vessel welds for the steam generator and pressurizer shall be conducted in accordance with ASME B&PV Code, 1983 Edition through the Summer 1983 Addenda, Articles IWB-2500 for Code Class 1.

Code Relief Request:

1 Pursuant to 10CFR50-55(a)(g)S(iii), relief is requested from performing i

the in-service volumetric examination on the inaccessible portions of the a

nozzle to shell welds of the steam generator and pressurizer.

Reason for Request

[

Geometric configuration of the. below listed nozzle to shell welds and their close proximity to one another limits the volume that can be

(,

examined.

Scanning is limited to one side only with a \\-V technique. Restriction on axial scan due to the close proximity of the welds to each other.

Pressurizer 1.

03-007-SW-A 4.

03-007-SW-D 2.

03-007-SW-B 5.

03-007-SW-E (Spray Nozzle) 3.

03-007-SW-C 6.

03-007-SW-S (Surge Nozzle)

Required volume not examinable ~ 80 percent.

Steam Generators:

Coverage is from both sides of weld with \\-V technique. Restriction on axial scan due to the steam generator supports integral extensions.

03-003-SW-V Inlet 03-005-SW-V Inlet 03-003-SW-LL Outlet 03-005-SW-LL Outlet 03-004-SW-V Inlet 03-006-SW-V Inlet 03-004-SW-LL Outlet 03-006-SW-LL Outlet l

Required volume not examinable ~ 10 percent.

(

LMW510301 i

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i Support for Relief: Alternate Exams 1.

Volumetric examination on the accessible portions will be performed 4

as required by ASME Section XI (IWB-2500). Any advances in UT techno-logy will be evaluated to determine its application for achieving maximum volume coverage and results.

2.

A system hydrostatic test will be performed once each inspection interval as required by Table IWB-2500-1, Category B-P.

3.

An in-service system leakage tests will be performed once each refueling outage per Category B-P, IWB-2500-1.

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~'N Millstone Nuclear Power Station Unit No. 3

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Relief From In-Service Inspection Requirements Relief Request:

IR-11 Code Class:

1 Examination Category:

B-J, Pressure Retaining Welds in Piping Item No.:

B9.10 Code Requirement:

For Millstone Unit No. 3, volumetric (ultrasonic) and surface examination of essentially 100 percent of the length of each Code Class 1 piping weld

>4" NPS shall be conducted in accordance with the ASME B&PV Code,Section XI, 1983 Edition through the Summer 1983 Addenda.

e Code Relief Request:

Pursuant to 10 CFR 50.55(a)(g)S(iii), relief is requested from performing

/'~,,*

the in-service volumetric examination of the inaccessible portions of the

(

welds listed in Table 1 (attached).

Reason for Relief:

Permanent structural interferences prohibit 100 percent volumetric examination coverage of the Code Required Volume (CRV). Relief is therefore requested from performing in-service examinations on the inaccessible portions of the volume required as noted in Table 1.

Tne subject welds received both volumetric examination by radiography and surface examinations during fabrication in accordance with ASME Section III requirements. Having met these requirements, adequate assurance of the structural integrity of the subject welds is provided.

Proposed Alternative Examinations:

A.

The subject welds will receive both a volumetric and surface examination on the accessible portions in-service in accordance with ASME Section XI (IWB-2500-1).

B.

An in-service hydrostatic test will be conducted successfully on the Class 1 Preservice Boundary, of which welds are a part thereof, per (IWB-2500-1 requirements).

C.

In-Service System Leak, age Tests will be performed per Category B-P, IWB-2500. Any advances in UT technology will be evaluated to determine its application for achieving maximum volume coverage and results.

TABLE I Code Category B-J Welds Data CRV Zone Weld Package Exam Percent Number Identification Number Material Type Angle Technique Configuration / Limitations Coverage 29 504-1-SW-2 UT-02-41 8" Sch 160 0*

Long. 3/2 Vee Structural Steel Column

~60%

SA-376/TP304 45' Restricts Access 30 504-3-SW-2 UT-02-202 8" Sch 160 0*

Long. 3/2 Vee Structural Steel Column

~60%

SA-346/TP304 45' Restricts Access 32 RCS-504D-FW-7-2M UT-02-189 8" Sch 160 0*

Long. 3/2 Vee Structural Steel Column 78%

SA-376/TP304 45*

Restricts Access I

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4.0 EVALUATION CRITERIA 4.1 Acceptance Standards 1983 Edition of Section XI through and including S83 Addenda.

CLASS 1 Examination Components and Part Acceptance Catego ry Examined Standard B-A Welds in Reactor Vessels IWB-3510 B-B Welds in Other Vessels IWB-3511 B-D Vessel Nozzle Welds IWB-3512 B-F, B-J Dissimilar & Similar Metal Welds IWB-3514 B-G-1 Bolting IWB-3515 B-H, B-K-1 Integral Attachments for Vessels, Piping, Pumps, &

Valves IWB-3516 B-L-1, B-M-1 Welds in Pumps & Valves IWB-3518 B-L-2, B-M-2 Pumps Casings & Valve Bodies IWB-3519 B-N Interior Surfaces & Internal Components of Reactor Vessels IWB-3520 B-0 Control Rod Drive Housing Welds IWB-3523 B-Q Steam Generator Tubing IWB-3521 4.2 Acceptance Standards CLASS 2 Article IWC-3000, Acceptance Standards for Flaw Indications, are in the course of preparation. The rules of IWB-3000 may be used.

Examination Components and Part Acceptance Category Examined Standard C-A Welds in Other Vessels IWB-3511 C-B Vessel Nozzle Welds IWB-3512 C-C Integral Attachments for Vessels, Piping, Pumps, &

Valves IWB-3516 C-D Bolting' IWB-3515 C-F Dissimilar and Similar Metal Welds IWB-3514 C-G Welds in Pumps & Valves IWB-3518 4.3 Acceptance Standards CLASS 3 Article IWD-3000, Acceptance Standards for Flaw Indications, are in the course of preparation. The rules of IWB-3000 may be used.

Examination Components and Part Acceptance Category Examined Standard D-A Integral Attachment Welds on Systems in Support of Reactor Shutdown Function IWB-3516 D-B Integral Attachment Welds on Systems in Support of ECC, CHR, Atmosphere Cleanup and RRR IWB-3516 D-C Integral Attachment Welds on Systems in Support of Residual Heat Removal From Spent Fuel Storage Pool IWB-3516 4.4 Acceptance Standard for Supports (Class 1, 2, and 3) 4.4.1 In-service snubber testing is not covered by this summary submittal as it is handled by the plant technical specifications.

4.4.2 Acceptance Standards (IWF-3400)

Acceptance Standards, to verify component support structural integrity, will be based on 1WF-3410.,

5.0 SUBMITTAL

SUMMARY

5.1 Description of ISI Plan Format The First Ten-Year In-service Inspection Plan Tables are being prepared for the examinations of the major components of the Millstone Unit 3 Nuclear Power Station.

The inspection plan sheets prepared for each component / system will list the examina-tions to be performed.

The inspection plan has been divided into smaller areas of interest called zones. Each zone is defined by a drawing which identifies and locates all the welds and other examination areas for that zone. The applicable inspection plan sheets accompanying each zone drawing provide the information necessary for qualified examiners to perform all the required examinations.

The inspection plan sheets contain the following information:

A.

Zone Data and Description This section contains the zone identification number, zone description, safety class, zone isometric number, number of items contained in the zone, and the number of individual examinations required within the zone.

B.

Examination Notes This section contains notes which provide additional information or instruction pertinent to the examinations to be performed on an individual weld of component, such as material specification.

In general, a single note will apply to several items.

C.

Line Item Number Each weld or component to be examined is assigned a unique line item number for the purpose of providing a uniform format identification.

Line item numbers are not provided for spool piece designations.

Spool piece numbers are included for information only.

D.

Examination Area Identification The examination area identification is the unique component or weld identification number assigned by the component fabricator, for longitudinal weld seams by Northeast Utilities, or in the case of field fabricated welds, by the component installer. These numbers also appear on the zone isometric drawings. _,

E.

Examination Area Description The examination area description is a brief description of the component to be examined or, in the case of a weld, the parts being joined.

F.

Exam Notes Identifies the examination note (s) which applies to eawa line item.

G.

Relief Requests Applicable Relief Request Numbers are listed here for each Exam Item that requires relief.

H.

Code Item Number Listed in this column are the appropriate item numbers from Table IWB-2500-1, IWC-2500-1, or IWD-2500-1, as applicable, of the ASME Boiler and Pressure Vessel Code,Section XI.

I.

Code Category Listed in this column are the appropriate categories from Table IWB-2500-1, IWC-2500-1, or IWD-2500-1, as applicable, of the ASME Boiler and Pressure Vessel Code,Section XI.

J.

Exam Method Listed in this column are the appropriate examination method (s) to be used for each examination item.

K.

Procedure Listed in this column are the appropriate examination procedures to be used for each examination item.

L.

Calibration Block Listed in this column is the appropriate code calibration block to be used for each examination item, if applicable.

M.

ISI Interval / Outage Listed in this column are the items that will be examined during the first Ten-Year Interval to meet NRC and Section XI requirements. The first integer denotes Inspection Interval (1 through 4) and the second integer denotes the refueling outage per interval.

I 5.2 Description of Summary Submittal Tables 5.2.1 The summary submittal tables (Section 7.2) A, B, & C for Class 1, 2, & 3, respectively, summarize by code category and code item number, the component to be examined and the method of examination. The tabulation of inspections of components have been compiled to fulfill the first ten years inspection requirements and to show compliance to the ASME B&PV Code,Section XI, 1983 Edition, through summer 1983 Addenda.

Where examinations stipulated by the code could not be performed completely, they were performe3 to the greatest extent possible and are considered to be in compliance with the applicable relief request, for the inaccessible areas, referenced.

Where no meaningful examination could be performed and exception to the requirements stipulated by the code were required, the applicable relief request is referenced.

5.2.2 Table D summarizes the hangers and supports subject to examination per IWF for Class 1, 2, & 3.

The breakdown is the same as 5.2.1 above.

All tables are developed based upon review of the "As-Built" Preservice Inspection Plan.

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i 6.0 RECORDS AND DATA MANAGEMENT 6.1 Records of the ISI Plan, schedules, calibration standards, examination procedures, examination results and reports, certifications, and corrective actions required and taken will i

be developed and maintained at MP-3 in accordance with IWA-6000 of ASME Section XI, as identified in NUSCO ISI Specific Plant, I

Procedures and QA Program, i

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7.0 FIGURES AND ATTAClfMENTS 7.1 Figures 7.'1.1 Examination Zone Boundaries 7.2 Attachment 7.2(A)

Class 1 NDE Summary Table 7.2(B)

' Class 2 NDE Summa'y Table r

7.2(C)~

Class 3 NDE Summary Table

7.2(D)

Class 1, 2, & 3 Component Support Summary Tables 3

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SUMMARY

CLASS 1 CODE

SUMMARY

j TABLE A CODE CATEGORY B-F CLASS PAGE PRESSURE RETAINING DISSIMILAR METAL WELDS 1 8 of 20 EXAM ASME SECTION XI RELIEF ITEM NO. ITEM DESCRIPTION METHOD COMPLIANCE REQUESTS 1 Heat Exhange B5.100 NPS >4" Vol. & Not Applicable N/A Surface B5.110 NPS <4" Surface Not Applicable N/A B5.120 Socket Welds Surface Not Applicable N/A Piping B5.130 Nominal Pipe Size >4" Dissimilar Metal Butt Vol. & Not Applicable N/A Welds Surface B5.140 Nominal Pipe Size <4" Dissimilar Metal Butt Surface Not Applicable N/A Welds B5.150 Dissimilar Metal Socket Welds Surface Not Applicable N/A r 5

MILLSTONE UNIT 3 ISI S'JtttARY CLASS 1 CODE SIR 9tARY i TABLE A I CODE CATEGORY B-G-1 PAGE PRESSURE RETAINING BOLTING GREATER THAN 9 of 20 [ 2" DIAMETER i EXAM ASME SECTION XI RELIEF ITEM NO. ITEM DESCRIPTION METHOD COMPLIANCE REQUESTS [ Reactor Vessel RCS { B6.10 Closure Head Nuts Surface In Compliance N/A B6.20 Closure Studs, in Place Vol. Not Applicable N/A B6.30 Closure Studs, when Removed Vol. & In Compliance N/A i Surface i B6.40 Threads in Flange Vol. In Compliance N/A B6.50 Closure Washers VT-1 In Compliance N/A l Pressurizer i l I B6.90 Steam Generators Not Applicable N/A i 1 1 B6.120 Heat Exchangers Not Applicable N/A l B6.150 Piping Not Applicable N/A ^

MILLSTONE UNIT 3 ISI SIMIARY CLASS 1 CODE SIMIARY TABLE A CODE CATEGORY B-G-1 CLASS PAGE PRESSURE RETAINING BOLTING GREATER TNAN 1 10 of 20 2" DIAMETER EXAM ASME SECTION XI RELIEF ITEM NO. ITEM DESCRIPTION METHOD COMPLIANCE REQUESTS Pumps B6.180 Bolts & Studs Vol. In Compliance N/A B6.190 Flange Surface, when VT-1 In Compliance IR-4 connection disassembled B6.200 Nuts, Bushings, Washers VT-1 In Compliance N/A Valves B.210 Bolts & Studs Vol. In Compliance N/A B6.220 Flange Surface, when VT-1 In Compliance IR-4 connection disassembled i B6.230 Nuts, Bushing, Washers VT-1 In Compliance N/A C n

MILLSTONE UNIT 3 ISI SIRetARY CLASS 1, CODE

SUMMARY

TABLE A CODE CATEGORY B-G-2 CLASS PAGE PRESSURE RETAINING BOLTING GREATER THAN 1 11 of 20 2" DIAMETER EXAM ASME SECTION XI RELIEF ITEM NO. ITEM DESCRIPTION METHOD COMPLIANCE REQUESTS Reactor Vessel B7.10 Bolts Studs, Nuts VT-1 Not Applicable N/A Pressurizer B7.20 Bolts, Studs, VT-1 In Compliance N/A Nuts VT-1 In Compliance N/A Steam Generators B7.30 Bolts, Studs VT-1 In Compliance N/A Nuts VT-1 In Compliance N/A B7.40 Heat Exchangers Not Applicable N/A y J

. ~. -. - - 4 MILLSTONE UNIT 3 ISI SUfftARY CLASS 1_ CODE SUfftARY l TABLE A I i i I CODE CATEGORY B-G-2 CLASS PAGE PRESSURE RETAINING BOLTING GREATER THAN 1 12 of 20 2 2" DIAMETER 4 i a EXAM ASME SECTION XI RELIEF ITEM NO. ITEM DESCRIPTION METHOD COMPLIANCE REQUESTS I Piping B7.50 Bolts, Studs, Nuts VT-1 In Compliance N/A Pumps l } B7.60 Bolts, Studs, Nuts VT-1 Not Applicable N/A I Valves i B7.70 Bolts, Studs, Nuts VT-1 In Compliance N/A i i CRD Housings j B7.80 Bolts, Studs, Nuts VT-1 Not Applicable N/A i i u i l

MILLSTONE UNIT 3 ISI

SUMMARY

CLASS 1, CODE

SUMMARY

TABLE A CODE CATEGORY B-H CLASS PAGE INTEGRAL ATTACHMENTS FOR VESSELS 1 13 of 20 EXAM ASME SECTION XI RELIEF ITEM NO. ITEM DESCRIPTION METHOD COMPLIANCE REQUESTS Reactor Vessel B8.10 Integrally Welded Vol. or Not Applicable N/A Attachments Surface Pressurizer B8.20 Integrally Welded Surface In Compliance N/A Attachments Steam Generator B.8.30 Integrally Welded Surface Not Applicable N/A Attachments Heat Exchangers BS.40 Integrally Welded Surface Not Applicable N/A Attachments ^

MILLSTONE UNIT 3 ISI SUff1ARY CLASS 1, CODE SIRf1ARY TABLE A i l CODE CATEGORY B-J CLASS PAGE DRESSURE RETAINING WELDS IN PIPING 1 14 of 20 I i l EXAM ASME SECTION XI RELIEF ITEM C3. ITEM DESCRIPTION METHOD COMPLIANCE REQUESTS i B9.10 Nominal Pipe Size >4" B).11 Circumferential Welds Surface & In Compliance IR-11 BS.12 Longitudinal Welds Vol. & Surface Not Applicable N/A 1 B9.23 Nominal Pipe Size <4" Surface B9.21 Circumferential Welds Surface In Compliance N/A I B9.22 Longitudinal Welds Surface Not Applicable N/A l B9.30 Branch Pipe Connection Welds l 89.31 Nonimal Pipe Size >4" Vol. & In Compliance N/A l Surface 1 l B9.31 Nominal Pipe Size >4" Vol. & In Compliance N/A l B9.32 Nominal Pipe Size >4" Surface In Compliance N/A l B9.40 Socket Welds Surface Not Applicable N/A I [ 4

MILLSTONE UNIT 3 ISI

SUMMARY

PIPE SUPPORT CODE

SUMMARY

TABLE D CODE CATEGORY F-B LINEAR TYPE SUPPORTS CLASS PAGE ALL 2 of 3 EXAM ASME SECTION XI RELIEF ITEM NO. ITEM DESCRIPTION METHOD COMPLIANCE REQUESTS i F-1,2,3,4 Class 1 Components VT-3 In Compliance N/A F-1,2,3,4 Class 2 Components VT-3 In Compliance N/A F-1,2,3,4 Class 3 Components VT-3 In Compliance N/A i ^

hlLLSTONE UNIT 3 ISI

SUMMARY

PIPE SUPPORT CODE

SUMMARY

TABLE D CODE CATEGORY F-C, COMPONENT STANDARD SUPPORTS CLASS PAGE ALL' 3 of 3 EXAM ASME SECTION XI RELIEF ITEM NO. ITEM DESCRIPTION METHOD COMPLIANCE REQUESTS F-1,2,3,4 Class 1 Components VT-3,4 In Compliance N/A F-1,2,3,4 Class 2 Components VT-3,4 In Compliance N/A F-1,2,3,4 Class 3 Components VT-3,4 In Compliance N/A c. r f - -}}

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